Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface / / prepared by Chunkuan Shih [and six others]

• Autore: Shih Chunkuan
• Pubblicazione: Washington, DC : , : U.S. Nuclear Regulatory Commission, , March 2016
• Descrizione fisica: 1 online resource (93 unnumbered pages) : color illustrations
• Soggetto topico: Nuclear power plants - Taiwan; Nuclear fuel rods - Thermal properties - Computer programs
• Note generali: Title from title screen (viewed on Mar. 31, 2016).; "Manuscript completed: August 2015; Date published: March 2016."; "Prepared as part of The technical exchange and cooperation between the U.S. Nuclear Regulatory Commission and the Task Force for Safety Critical Software in the Field of Nuclear Safety Research."
• Nota di bibliografia: Includes bibliographical references (page 6-1).
• Titolo autorizzato: Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Lingua di pubblicazione: Inglese
• Record Nr.: 9910707042303321
• Lo trovi qui: Univ. Federico II